Determining the volumetric steam content in a BWR gravity leg
Journal Article
·
· Sov. At. Energy (Engl. Transl.); (United States)
The structure of two-phase flow in a large-diameter limited-height gravity leg was investigated in the VK-50 reactor. Phase distribution properties and a physical model of the steam-water mixture flow in the gravity leg were described. On the basis of experimentally derived date a method was proposed for the calculation of volumetric steam content in the leg.
- OSTI ID:
- 5284331
- Journal Information:
- Sov. At. Energy (Engl. Transl.); (United States), Vol. 62:3; Other Information: Translated from At. Energ.; 62: No. 3, 158-160(Mar 1987)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR COOLING SYSTEMS
FLOW MODELS
TWO-PHASE FLOW
STEAM
VOLUME
VK-50 REACTOR
DIMENSIONS
FLOW RATE
HEAT TRANSFER
HYDRAULICS
HYDROSTATICS
MIXTURES
SPATIAL DISTRIBUTION
WATER
BWR TYPE REACTORS
COOLING SYSTEMS
DISPERSIONS
DISTRIBUTION
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
MECHANICS
OXYGEN COMPOUNDS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
REACTOR COOLING SYSTEMS
FLOW MODELS
TWO-PHASE FLOW
STEAM
VOLUME
VK-50 REACTOR
DIMENSIONS
FLOW RATE
HEAT TRANSFER
HYDRAULICS
HYDROSTATICS
MIXTURES
SPATIAL DISTRIBUTION
WATER
BWR TYPE REACTORS
COOLING SYSTEMS
DISPERSIONS
DISTRIBUTION
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
MECHANICS
OXYGEN COMPOUNDS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled